Letter Sequence Response to RAI |
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EPID:L-2020-LLA-0004, Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02) (Open) |
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MONTHYEARCNL-19-066, Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02)2020-01-14014 January 2020 Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02) Project stage: Request CNL-20-026, Supplement to Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02)2020-02-18018 February 2020 Supplement to Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02) Project stage: Supplement ML20054B5532020-02-20020 February 2020 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Acceptance of License Amendment Request to Modify the UFSAR Based on a New Hydrologic Analysis Project stage: Acceptance Review ML20106F1042020-04-14014 April 2020 Request for Additional Information Regarding the Hydrologic Analysis LAR Project stage: RAI CNL-20-032, Response to Request for Additional Information (TS-19-02) Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis2020-05-14014 May 2020 Response to Request for Additional Information (TS-19-02) Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis Project stage: Response to RAI ML20141L7672020-05-28028 May 2020 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML20189A2112020-07-0101 July 2020 Request for Additional Information Regarding Hydrologic UFSAR Update Project stage: RAI ML20203M0572020-07-16016 July 2020 Updated TVA Non-Proprietary Slides for Open Session of July 16, 2020, Partially Closed Public Meeting to Discuss Sequoyah License Amendment Request Project stage: Meeting ML20196L7922020-07-16016 July 2020 Corrected TVA Non-Proprietary Slides for Open Session of July 16, 2020, Partially Closed Public Meeting to Discuss Sequoyah License Amendment Request Project stage: Meeting ML20196L6892020-07-16016 July 2020 TVA Non-Proprietary Slides for Open Session of July 16, 2020, Partially Closed Public Meeting to Discuss Sequoyah License Amendment Request Project stage: Meeting ML20203M2292020-08-11011 August 2020 July 16, 2020, Summary of Partially Closed Meeting with Tennessee Valley Authority to Discuss Responses to Requests for Additional Information Regarding Updated Final Safety Analysis Report Hydrologic Analysis License Amendment Request Project stage: RAI CNL-20-057, Tennessee Valley Authority - Application to Revise Sequoyah Nuclear Plant Units 1 & 2 Updated FSAR Changes to Hydrologic Analysis - Partial Response to Additional Request for Additional Information (TS-19-02)2020-08-12012 August 2020 Tennessee Valley Authority - Application to Revise Sequoyah Nuclear Plant Units 1 & 2 Updated FSAR Changes to Hydrologic Analysis - Partial Response to Additional Request for Additional Information (TS-19-02) Project stage: Request ML20261H4162020-09-0202 September 2020 NRR E-mail Capture - Draft Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, Request to Revise UFSAR Hydrologic Analysis Project stage: Draft RAI ML20261H4182020-09-14014 September 2020 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Audit Plan and Setup of Online Reference Portal Project stage: Other ML20261H4172020-09-14014 September 2020 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Hydrologic UFSAR Update Project stage: RAI ML20293A0802020-10-28028 October 2020 Summary of October 13, 2020, Closed Meeting with TVA on Responses to Requests for Additional Information Updated Final Safety Analysis Report Hydrologic Analysis License Amendment Request Project stage: RAI ML20316A0182020-11-10010 November 2020 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Audit Plan and Setup of Online Reference Portal Project stage: Other CNL-20-082, Partial Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (TS-19-02)2020-11-10010 November 2020 Partial Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (TS-19-02) Project stage: Response to RAI ML20343A1182021-01-12012 January 2021 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML21068A4082021-03-0909 March 2021 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Supplement 2 to Audit Plan and Setup of Online Reference Portal Project stage: Other CNL-21-024, Partial Response to Additional Request for Information Re Application to Revise Updated Final Safety Analysis Report Re Changes to Hydrologic Analysis (TS-19-02)2021-06-15015 June 2021 Partial Response to Additional Request for Information Re Application to Revise Updated Final Safety Analysis Report Re Changes to Hydrologic Analysis (TS-19-02) Project stage: Request ML21239A1152021-08-13013 August 2021 Partial Response to Additional Request for Additional Information, (Question 2) Regarding Application to Revise Sequoyah Nuclear Plant, Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Correction Project stage: Request CNL-21-095, Submittal of Application to Revise Sequoyah Nuclear Plant, Units 1 and 2, 10 CFR 50.90 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Software Dedication Report 16-01 - Update .2021-12-21021 December 2021 Submittal of Application to Revise Sequoyah Nuclear Plant, Units 1 and 2, 10 CFR 50.90 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Software Dedication Report 16-01 - Update . Project stage: Request CNL-23-012, Revision to the Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02)2023-04-11011 April 2023 Revision to the Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02) Project stage: Request 2020-07-16
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Category:Letter type:CNL
MONTHYEARCNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-23-068, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-012, Revision to the Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02)2023-04-11011 April 2023 Revision to the Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report CNL-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding Status Report CNL-23-021, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-03-0808 March 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-23-003, Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A2023-01-30030 January 2023 Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A CNL-23-011, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements2023-01-18018 January 2023 Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements CNL-23-009, Response to Request for Additional Information Request to Revise Technical Specification 3.4.122023-01-0404 January 2023 Response to Request for Additional Information Request to Revise Technical Specification 3.4.12 CNL-23-008, Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-12-22022 December 2022 Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-106, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operat2022-11-28028 November 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operatio CNL-22-099, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2022-10-31031 October 2022 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-22-104, Correction to Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-022022-10-31031 October 2022 Correction to Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02 CNL-22-098, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 552022-10-17017 October 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 55 CNL-22-084, Response to Request for Additional Information Regarding License Amendment Request to License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07)2022-09-16016 September 2022 Response to Request for Additional Information Regarding License Amendment Request to License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07) CNL-22-085, Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Al2022-09-0202 September 2022 Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alte CNL-22-053, Response to Request for Additional Information Regarding Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Second Partial Response to Additional Requ2022-08-22022 August 2022 Response to Request for Additional Information Regarding Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Second Partial Response to Additional Reques CNL-22-077, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-08-11011 August 2022 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-030, Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03)2022-07-27027 July 2022 Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03) CNL-22-080, Request for Enforcement Discretion from the Requirements of Technical Specification 3.5.2, ECCS - Operating2022-07-22022 July 2022 Request for Enforcement Discretion from the Requirements of Technical Specification 3.5.2, ECCS - Operating CNL-22-081, Supplement to Sequoyah Nuclear Plant, Unit 1, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-122022-07-21021 July 2022 Supplement to Sequoyah Nuclear Plant, Unit 1, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-12 CNL-22-079, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-122022-07-20020 July 2022 American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RP-12 CNL-22-071, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08)2022-07-13013 July 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08) CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) CNL-22-069, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf.2022-07-0101 July 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. CNL-22-070, Status Regarding the Improved Flood Mitigation System Project2022-06-30030 June 2022 Status Regarding the Improved Flood Mitigation System Project CNL-22-062, Response to Request for Additional Information Regarding American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-022022-06-28028 June 2022 Response to Request for Additional Information Regarding American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02 CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022 and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change CNL-22-068, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-06-0808 June 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-047, Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2022-05-23023 May 2022 Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-22-034, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03)2022-05-13013 May 2022 Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03) CNL-22-027, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 40 - Annual Update and Proposed Changes to Revision 402022-04-28028 April 2022 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 40 - Annual Update and Proposed Changes to Revision 40 CNL-22-023, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf2022-04-28028 April 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf 2024-01-17
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML24004A0402024-01-0303 January 2024 Response to NRCs November 8, 2023, Request for Additional Information - Related to Independent Spent Fuel Storage Installation ML23117A1162023-04-27027 April 2023 Response to Follow-up Questions to TVAs Response to NRCs Request for Supplemental Information (Rsi) Related to August 4, 2022, Sequoyah ISFSI Exemption Request CNL-23-009, Response to Request for Additional Information Request to Revise Technical Specification 3.4.122023-01-0404 January 2023 Response to Request for Additional Information Request to Revise Technical Specification 3.4.12 ML22353A0662022-12-19019 December 2022 Response to Request for Supplemental Information (D-RSI) Request for Exemption from Non-Destruction-Examination Compliance CNL-22-084, Response to Request for Additional Information Regarding License Amendment Request to License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07)2022-09-16016 September 2022 Response to Request for Additional Information Regarding License Amendment Request to License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07) CNL-22-085, Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Al2022-09-0202 September 2022 Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alte CNL-22-053, Response to Request for Additional Information Regarding Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Second Partial Response to Additional Requ2022-08-22022 August 2022 Response to Request for Additional Information Regarding Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Second Partial Response to Additional Reques CNL-22-069, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf.2022-07-0101 July 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. CNL-22-062, Response to Request for Additional Information Regarding American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-022022-06-28028 June 2022 Response to Request for Additional Information Regarding American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alternative RV-02 CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change CNL-21-024, Partial Response to Additional Request for Information Re Application to Revise Updated Final Safety Analysis Report Re Changes to Hydrologic Analysis (TS-19-02)2021-06-15015 June 2021 Partial Response to Additional Request for Information Re Application to Revise Updated Final Safety Analysis Report Re Changes to Hydrologic Analysis (TS-19-02) CNL-21-039, Response to Request for Additional Information Re Application to Modify Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09)2021-05-0505 May 2021 Response to Request for Additional Information Re Application to Modify Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09) CNL-20-082, Partial Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (TS-19-02)2020-11-10010 November 2020 Partial Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (TS-19-02) CNL-20-076, Response to Request for Additional Information Re Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01)2020-09-23023 September 2020 Response to Request for Additional Information Re Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01) CNL-20-057, Tennessee Valley Authority - Application to Revise Sequoyah Nuclear Plant Units 1 & 2 Updated FSAR Changes to Hydrologic Analysis - Partial Response to Additional Request for Additional Information (TS-19-02)2020-08-12012 August 2020 Tennessee Valley Authority - Application to Revise Sequoyah Nuclear Plant Units 1 & 2 Updated FSAR Changes to Hydrologic Analysis - Partial Response to Additional Request for Additional Information (TS-19-02) ML20196L6892020-07-16016 July 2020 TVA Non-Proprietary Slides for Open Session of July 16, 2020, Partially Closed Public Meeting to Discuss Sequoyah License Amendment Request CNL-20-032, Response to Request for Additional Information (TS-19-02) Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis2020-05-14014 May 2020 Response to Request for Additional Information (TS-19-02) Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis CNL-20-026, Supplement to Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02)2020-02-18018 February 2020 Supplement to Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02) CNL-19-119, Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Unit 1 Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05)2019-11-19019 November 2019 Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Unit 1 Exigent License Amendment Request to Revise Technical Specification 4.2.2, Control Rod Assemblies (SQN-TS-19-05) CNL-19-061, Seismic Probabilistic Risk Assessment for Sequoyah Nuclear Plant, Units 1 and 2 - Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task2019-10-18018 October 2019 Seismic Probabilistic Risk Assessment for Sequoyah Nuclear Plant, Units 1 and 2 - Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Fo ML19231A2082019-08-19019 August 2019 Response to Request for Information Regarding Unit 2 Cycle 22 - 180-Day Steam Generator Tube Inspection Report CNL-19-068, Response to Request for Additional Information Regarding the Sequoyah Nuclear Plant (SQN) Units 1 and 2 and Watts Bar Nuclear Plant (WBN) Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for2019-07-22022 July 2019 Response to Request for Additional Information Regarding the Sequoyah Nuclear Plant (SQN) Units 1 and 2 and Watts Bar Nuclear Plant (WBN) Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for .. CNL-19-057, Response to Request for Additional Information Regarding American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection Program, Request for Alternative, 18-ISl-12019-06-19019 June 2019 Response to Request for Additional Information Regarding American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection Program, Request for Alternative, 18-ISl-1 CNL-19-002, Response to Request for Additional Information Regarding Application to Modify Sequoyah Nuclear Plant Units 1 and 2, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures,.2019-03-21021 March 2019 Response to Request for Additional Information Regarding Application to Modify Sequoyah Nuclear Plant Units 1 and 2, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures,. CNL-19-016, Response to Request for Additional Information on License Amendment Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise the Updated Final Safety Analysis Report2019-01-30030 January 2019 Response to Request for Additional Information on License Amendment Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise the Updated Final Safety Analysis Report CNL-18-089, Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-0342018-07-23023 July 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plan Update for Browns Ferry Nuclear Plant and Sequoyah Nuclear Plant Independent Spent Fuel Storage Installations, Docket Nos. 72-052 and 72-034 NL-18-044, Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Pre2018-04-19019 April 2018 Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Prec CNL-18-044, Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation.2018-04-19019 April 2018 Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation. CNL-17-063, Response to Request for Additional Information (RAI) Regarding Application to Modify Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02)2017-10-26026 October 2017 Response to Request for Additional Information (RAI) Regarding Application to Modify Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02) CNL-17-104, Response to Request for Additional Information Regarding Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04)2017-08-0707 August 2017 Response to Request for Additional Information Regarding Proposed Technical Specification Change to Revise the Note Modifying SR 3.8.1.17 of TS 3.8.1 AC Sources - Operating (TS-SQN-16-04) CNL-17-098, Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-27027 July 2017 Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-085, Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-0707 July 2017 Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-039, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Withdrawal of Regulatory..2017-03-10010 March 2017 Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Withdrawal of Regulatory.. CNL-16-194, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid2016-12-23023 December 2016 Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid CNL-16-178, Response to Request for Additional Information (RAI) Regarding Application to Modify Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02)2016-12-23023 December 2016 Response to Request for Additional Information (RAI) Regarding Application to Modify Technical Specifications Regarding Diesel Generator Steady State Frequency (SQN-TS-14-02) CNL-16-196, Revised Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2016-12-19019 December 2016 Revised Response to NRC Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools CNL-16-123, Response to NRC Request for Additional Information Request for Approval for Use of Alternate Calibration Block Reflector Requirements 16-PDI-52016-07-28028 July 2016 Response to NRC Request for Additional Information Request for Approval for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5 CNL-16-086, Response to Request for Additional Information Technical Specifications 3.7.8 Change - Essential Raw Cooling Water System2016-05-31031 May 2016 Response to Request for Additional Information Technical Specifications 3.7.8 Change - Essential Raw Cooling Water System CNL-15-218, Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) (TAC Nos. MF5366 and MF5367), Supplement to Response to Request for Additional Information2015-10-23023 October 2015 Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) (TAC Nos. MF5366 and MF5367), Supplement to Response to Request for Additional Information CNL-15-171, Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) - Response to Request for Additional Information2015-09-11011 September 2015 Application to Revise Technical Specification 6.8.4.h, Containment Leakage Rate Testing Program, (SQN-TS-14-03) - Response to Request for Additional Information CNL-15-158, Supplement to TVA Letter, Sequoyah Nuclear Plant - Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor.2015-08-0303 August 2015 Supplement to TVA Letter, Sequoyah Nuclear Plant - Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor. CNL-15-146, Response to NRC Request for Information Regarding the Review of the License Renewal Application, Set 25 (TAC Nos. MF0481 and MF0482)2015-08-0303 August 2015 Response to NRC Request for Information Regarding the Review of the License Renewal Application, Set 25 (TAC Nos. MF0481 and MF0482) NL-15-158, Supplement to TVA Letter, Sequoyah Nuclear Plant - Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor.2015-08-0303 August 2015 Supplement to TVA Letter, Sequoyah Nuclear Plant - Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor. CNL-15-136, Response to NRC Request for Additional Information Regarding ASME Request for Relief RP-072015-07-22022 July 2015 Response to NRC Request for Additional Information Regarding ASME Request for Relief RP-07 ML15176A6822015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 4 of 8 ML15176A6812015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 3 of 8 ML15176A7482015-06-19019 June 2015 Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 8 of 8 ML15176A7402015-06-19019 June 2015 Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 8 ML15176A6792015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 2 of 8 ML15176A6642015-06-19019 June 2015 Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 1 of 8 2024-01-03
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SECURITY RELATED INFORMATION AND PROPRIETARY INFORMATION -
. . . WITHHOLD UNDER 10 CFR 2.390 _
This lette.r ~ d~ntrolled when separated from Enclosure 2 um Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-20-082 November 1o, 2020 10 CFR 50.90 .
ATTN: Document Control Desk u:s. Nuqlear Regulatory Commission Washington, D.C. 20555-000'1 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility License Nos. DPR:-77 and. DPR-79 NRG Docket Nos. 50-327 and 50-328 *
Subject:
Partial Response to Request for Additional Information Regarding Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final
. Safety Analysis Report Regarding Changes to Hydrologlc Analysis (TS-19-02) (EPID L-2020-LLA-0004) .
References:
- 1. TVA Letter to NRG, CNL-19-066, "Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding -
- Changes to .Hydrologlc Analysis (TS-19-02)," dated January 14, 2020 * *
(ML20016A396 and ML20016A397}
- 2. TVA Letter to NRG, CNL-20-026, "Supplement to Application to Revise -
Sequoyah Nuclear Plant L)nits 1 and 2 Wpdated Final Safety Analysis Report Regarding Changes to Hydrologic *Analysis, (TS-19-02)
(EPID L-2020-LLA-0004)," dated February 18, 2020 (ML20049H184)
- 3. TVA Letter to NRG, CNL~20-032, "Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Response to Request for Additional Information (TS-19-02) (EPID L-2020-LLA-0004)," d~ted May 14, 2020 (ML20135H.067) - -
- 4.
.SECURITY-RELATED INFORMATION_ AND PROPRIETARY INFORMATION-
.. : ** WITHHOLQ UNDER 10 CFR 2.390 .
This l~r Is_ deco~lled when-separat~ from Enclosure 2
SECURITY RELATED INFORMATION AND PROPRIETARY INFORMATION-
. - WITHHOLD UNDER 10* CFR 2.390 This *letter is decontrolled when se~rated :from Enclosure 2 U.S. Nuclear Regulatory Commission CNL-20-082 Page2 November 1.0, 2020
- 5. NRC Electronic Mail to TVA, "Sequoyah Nuclear Plant, Units 1 and 2 -
Request for Additional Information Regarding Hydrologic UFSAR _Update (EPIO L-2020-LLA-0004 }, " dated September 14, 2020 (ML20261. H417}
- 6. NRC letter to TVA, *summary of October 13, 2020, Closed Meeting with Tennessee Valley Authority to Discuss Responses to Requests for Additional Information ~egarding Updated Final Safety Analysis Report Hydrologi*c
- Analysis License Amendment Request '(EPID L-2020-LLA-0004}," dated October 27, 2020 (ML20293A080} .
- 7. NRC Electronic Mail to TVA, "RE: Sequoyah Hydrologic UFSAR LAR-Proposed Schedule for EXHB RAI responses," dated November 3~ 2020 In Reference .1, Tennesse.e V~lley Authority (TVA} submitted a requ~st for an amendment to Renewed Facility Operating License Nos. DPR-77 and DPR-79 for Sequoyah Nuclear _
Plant (SQN} Units 1 and 2, respectively: This license amendment request (LAR} revises the SQN Units 1 a_nd 2, Updated Final Safety Analysis Report (UFSAR} to reflect the results from the new hydrologic analysis. TVA determined that the propc:,sed changes to the SQN UF$AR require prior Nu.clear Regulatory Commission (NRC} approval.
In References 2, 3, and _4, TVA provided supplements to Reference 1. In Reference 5, the NRC provided a request for additional information (RAI}. Following receipt of Reference 5, TVA determined that there was an unyerifled assumption in the calculations COJ"!cemlng the Apa_lachia barn* failure analysis and entered this issue into the TVA corrective action program.
TVA communicated this information to the NRC during a closed public meeting on -
October 13, 2020 (Reference 6). Because this Apalachla barn unverified assumption affects some of the flies requested by the NRC in Reference 5, TVA Is providing a partial response to Reference 5. Specifically, *Enclosure 1 -to this letter provides the responses to the RAI in Reference 5 with ~he exception of RAI 2.4-2.3.b and RAI 2A-4. For RAI 2.4-2.3.b, the parent calculation that provides the requested information Is affected by the Apalachia Dam Issue and will ~ revised. However, the Probable Maximum Precipitation (PMP} Basin pepth is not affected. Therefore, a partial response for RAI 2.4-2.3.b has been provided in Enclosure 1 that addresses PMP Basin depth. The remaining response to RAI 2.4-2.3.b and the response to RAJ- 2.4-4 will be provided at a later date..
- In Reference 5, the NRC requested that TVA respond to the RAI by October 14, 2020 ..
However, as noted in Reference 7, the partial response date for this RAI was extended to November 11, 2020.
SECURITY RELATED INFORMATION AND PROPRIETARY-INFORMATION -
. WITHHOLD UtilDER 10 CFR 2.390 This letter Is decontrol_led when-separated ~m. Enclosure 2
SECURJTY*RELATED INFORMATION AND PROPRIETARY INFORMATION-
. . WITHHOLD UNDER 10 CFR 2.390 .
This letter Is decontrolled *when separated from Enclosure 2 U.S. Nuclear Regulatory Commission CNL-20--082 Page 3 November 10, 2020 As indicated in Enclosure 1, the information requested by the NRQ Is contained in Enclosure 2, which contains a digital versatile disc (DVD). Enclosure 2 contains security related-information that TVA Is requesting be withheld from public disclosur~ in accordance with 1b CFR 2.390. . provides *a flowchart aid to facilitate :µie understanding of the Interactions of the.
various TVA calculations U,at make up the SQN hydrology analyses. In support of the.
RAI 2.4-2.2.c response, Enclosure 2 also contains the Barge Design Solutions (Barge) Software Dedication Report (SDR), PMP Evaluation Tool Package, SDR 16-01, Revision 2. The ~DR, in Its entirety, contains information that Barge considers to be proprietary pursuant to Title 10 of the Code of Federaf Regulations (1 0 CFR) 2.390, RPublic fnspectlon.s, exemptions, requests for*
withholding,R paragraph (a)(4). Enclosure 4 provides the Barge affidavit supporting this proprietary withholding request. The affidavit sets forth the'basis on which the information
- may be.withheld from public disclosure by the NRC and addresses with specificity the
- considerations listed in paragraph (b)(4) of 10 CFR 2.390. Accordingly, TVA requests that the information Which Is proprietary to Barge be withheld from public. disclosure In accordance with 10 CF.R 2.390. Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Barge Design Solutions* affidavit should reference*
SDR 16--01, dated September 2020, and should be addressed to Ms. Carrie Stokes, Senior Vice President, Barge Design Solutions Inc., 615 3 rd _Avenue South, Suite 700, Nashville, TN 37210.
T,his letter does not change the no significant-hazard considerations nor the environmental
~nsiderations contained in Reference 1. *Additionally, in accordance with 10 CFR 50.91(b)(1),
TVA is sending a copy of this letter and the enclosure to the Tennessee Department <;>f Environment and Conservation.
- There are no new regulatory commitments associated with this submittal,. Please address any questions regarding this submittal to Gordon Williams, Senior Manager, Fleet Licensing (Acting), at 423-751-2687. * *
- I declare under penalty of perjury thaf the foregoing is true and correct: Executed on this 10th day of November 2020.
Respectfully,
%-z'-r~-
James T. Polickoski Director; Nuclear Regulatory Affairs Enclosures cc: See Page 4 SECURITY RELATED INFORMATION AND PROPRIETARY INFORMATION -
WITHHOLD UNDER 10 CFR 2.390 .
This letter Is decontrolled when separated from Enclosure 2
SECURITY RELATED INFORMATION AND P.ROPR,ETARY INFO.RMATIO'N -
This letter is. decontrolled when separated ~m 'Encl0$ure 2 U.S. Nuclear R~gulatory Commission CNL-20-082 Page4 November 10, 2020
Enclosures:
- 1. Response to. NRG Additional Request for Additional Information
- 2. DVD Co.ntaining the lnfonnation Requested in Enclosure 1 (Security Related and Proprietary Information) .
- 3. Flowchart of Calculations
- 4. Barge Design Solutions Affidavit cc (w/o Enclosure 2):
NRG Regional Administrator - Region .II .
NRG Senior Resident ln.spector- Sequoyah Nuclear Plant, Units 1 and 2 NRG Project Manager - Sequoyah Nuclear Plant Director, Division of Radiological Health - Tennessee State Department of Environment
SECURITY RELATED INFORMATION AND PROPRIETARY INFORMATION -
. WITHHOLD UND.ER:10 QFR 2:390 .
This letter is decontrolled when separated from Enclosure .2
Enclosure 1 Response to NRC Additional Request for Additional Information (RAI)
RAJ 2.4-2: PMP Input/Output Files Section 2.4.3, "PMP [Probable Maximum Precipitation] on Streams and Rivers* of the proposed Updated Final Safety Analysis Report (UFSAR) revision present the revised flood hazard estimations at the plant site due to riverine flooding. NUREG-0800, *Standard Review Plan
[SRP] for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Ught-water Reactor] Edition," Revision 4, Section 2.4.3, "Probable Maximum Flood (PMF) on Streams and Rivers* (Agencywide Documents Access and Management System (ADAMS) Accession No. ML070730405), and Regulatory Guide (RG) 1.59, "Design Basis Floods for Nuclear Power Plants" (ADAMS Accession No. ML003740388), provide guidelines for estimating this flood causing mechanism. After reviewing the license amendment request (LAR) and enclosed documents, the NRG staff has determined that it needs additional information related to estimating this flood causing mechanism to independently verify the licensee's proposed change. Therefore, the NRG staff requests all PMP input/output files be provided, as summarized in Figure No. 1 of "Response to NRG IQVB Request for Additional Information" (ADAMS Accession No. ML20135H067), including:
- 1. Input Information
- a. User input (including storm types, durations, basins of interest)
- b. ArcG/S base Python script
- c. Tennessee Valley Authority (TVA) Project sub-basins shapefi/e
- d. Sub-basin geographic information system (GIS) encapsulating shapefi/e of TVA subbasins, shapes, area; and positions
- 2. Gridded PMP Point Data Development - Dedicated Software
- a. Sub-basin text file of user input
- b. Event specific Python script
- c. Modified PMP Evaluation Tool scripts and associated documentation
- d. Gridded PMP Point Data used for local intense precipitation (LIP) and PMF
- 3. Non-QA GIS Software Tools - Alternate ArcGIS Calculations
- a. Python scripts for creating Triangular Irregular Network (TIN) and utilizing Polygon Volume Tool
- b. ArcG/S sub-basin weighted average PMP depths for controlling PMF scenario CNL-20-082 E1-1 of 4
Enclosure 1 TVA Response to RAJ 2.4-2 The requested information is provided in the following files on the digital versatile disc (DVD) In to this submittal.
1.a User Input
- Storm Types are located in calculation CDQ0000002016000041, Section 3.3.
- Duration is located in calculation CDQ0000002015000034, Temporal Distribution Calculation.
- Basins are located in calculation CDQ0000002016000044, Appendix A-A.
1.b ArcGIS Base Python Script is located in calculation CDQ0000002016000044 Appendix A-F.
1.c Project sub-basins are located in calculation CDQ0000002016000044, Appendix A-A.
1.d The full TVA basin Information is located in calculation CDQ0000002016000044, Appendix A-B.
2.a Sub-basin Text File is located in calculation CDQ0000002016000044, Appendix A-D.
2.b The Event Specific Python Script is located in calculation CDQ0000002016000044, Appendix A-D.
2.c The Modified PMP Tool Script is located in the PMP Tool software dedication report (SOR) Revision 2, Attachment 9.
2.d. PMP data used for LIP is located in calculation CDQ0000002016000041, Section 5.4.4, Table 14. PMP data used for PMF is found in calculation CDQ0000002016000044, Appendix A.
3.a. The script for generating the TIN and utilizing the polygon volume tool, which are part of the process to calculate primary basin rainfall, is located in CDQ0000002016000044 Appendix A-D.
3.b. PMP Basin Depth for the Controlling PMF is located in calculation CDQ0000002017000059. This calculation is affected by the dam safety issue at Apalachia Dam; however, the PMP basin depth is not affected. The precipitation files for each of the four Chickamauga simulations is provided In Enclosure 2. These files are labeled as CHH_01_HourlyDistributions.csv, CHH_02_HourlyDistributions.csv, CHH_03_Hourly Distributions.csv, and CHH_04_HourlyDistributions for Chickamauga simulations 1 through 4, respectively, on Enclosure 2 DVD.
Calculation CDQ0000002017000059 will be formally transmitted to the NRC in its entirety once the Apalachia dam issue is resolved. to this submittal provides a flowchart aid to facilitate the understanding of the interactions of the various TVA calculations that make up the SQN hydrology analyses. Page three of Enclosure 3 details the sources of the requested information, lists the RAI number for which the data are being provided, and illustrates the predecessor and successor relationships between calculations that present the PMP analysis. The flow chart should be reviewed before utillzlng the data on the DVD.
CNL-20-082 E1-2 of 4
Enclosure 1 RA/ 2.4:3: LIP Modeling Input/Output Flies Section 2.4. 2, "Floods" of the proposed UFSAR revision presents the revised flood hazard estimations at the plant site due to LIP flooding. SRP Section 2.4.2, "Floods" (ADAMS Accession No. ML070100647), provides guidelines for estimating this flood causing mechanism.
After reviewing the submitted LAR and enclosed documents, the NRG staff has determined that it needs additional Information related to estimating this flood causing mechanism to Independently verify the 1/censee's proposed change. Therefore, the NRG staff requests all UP mode/Ing input/output files be provided, including:
- LIP hydrodynamic model input/output files for slmula'flng local intense precipitation surface ronoff, routing, and flooding.
TVA Response to BAI 2,4:3 The requested lnfonnation is provided In the following files on the DVD in Enclosure 2.
- The LIP model input/output files for simulating LIP surface runoff, routing, and flooding are located in calculation GDQ0000002013000057, Appendix F.
- The LIP rainfall depth input information used in the model is contained in calculation CDQ0000002016000041, Section 5.4.4, Table 14.
RAJ 2.4--4: PMF Modeling Input/Output Files Section 2.4.3, "PMF Flood In Rivers and Streams" of the proposed UFSAR revision presents the revised flood hazard estimations at the plant site due to LIP flooding. SRP Section 2.4.3 provides guidelines for estimating this flood causing mechanism. After reviewing the license amendment request (LAR) and enclosed documents, the NRG staff determined that it needs additional information related to estimating this flood causing mechanism to independently verify the licensee's proposed change. Therefore, the NRG staff requests all modeling input/output data files be provided for controlling PMF (with hydro/ogic dam failures) scenario, including:
- 1. Tabular data associated with "the controlling primary and secondary area nesting sequence and the controlling PMP rainfall depth spatial distribution over the watershed" (LAR Enclosure, Section 2.4.3. 1) as well as executable version of the tools (If any) used to distribute the gridded PMP values Into subbasln space and time:
- a. LAR Enclosure 3, Figure 2.4.3-1
- b. LAR Enclosure 3, Figure 2.4.3-5a (as provided in LAR Enclosure 4, Table 2.4.3-1)
- 2. Executable version of sub-basin unit hydrograph calculations (as referenced in LAR Enclosure 4, Section 2.4.3.3), as well as electronic version of data shown in LAR Enclosure 3, Figure 2.4.3-6.
- 3. Executable version of calculation files (if applicable) for estimating precipitation excess (as referenced In LAR Enclosure 4, Section 2.4.3.2).
- 4. Shapeflles (or similar locational data) for HEC-RAS model limits, river gage, Sequoyah plant site and dam locations, as shown in LAR Enclosure 3, Figure 2.4.3-4 and Figure 2.4.3-5 (as referenced in LAR Enclosure 4, Section 2.4.3.3)
CNL-20-082 E1-3 of 4
Enclosure 1
- 5. Executable version of the runoff and HEC-RAS model files, including HEC-RAS Inputs such as calibrated geometry, unsteady flow rules and inflows (as referenced in LAR Enclosure 4, Section 2.4.3.3).
TVA Response to RAI 2.4-4 The requested information is provided in calculations that are affected by the Apalachia Dam safety issue. Therefore, TVA will provide a response to this RAI at a later date.
RA/ 2.4-5: Seismic Dam Failure Modeling Input/Output Files Section 2.4.4, "Potential Dam Failures, Seismically lnducedn of the proposed UFSAR revision in the application presents the revised flood hazard estimations at the plant site due to seismic dam failure flooding. SRP Section 2.4.3 provides guidelines for estimating this flood causing mechanism. After reviewing the license amendment request (LAR) and enclosed documents, the NRG staff detennined that It needs additional infonnation related to estimating this flood causing mechanism to independently verify the licensee's proposed change. Therefore, the NRG staff requests all modeling input/output data files be provided for controlling seismic dam failure scenario, including:
- 1. Hydrologic Engineering Center River Analysis System simulation setup, input and output files for four potentially critical seismic-flood event combinations (as referenced in LAR Enclosure 4, Section 2.4.4.2).
- 2. Calculations for 25-year and 500-year flood inflows (as referenced in LAR Enclosure 4, Section 2.4.4. 1)
TVA Response to RAI 2.4-5 The requested information is provided in the following files on the DVD in Enclosure 2.
- 1. The Seismic Hydraulic Engineering Center River Analysis System (HEC-RAS) files for the input and output files for the four potentially critical seismic-flood event combinations (as referenced in LAR Enclosure 4, Section 2.4.4.2) are located In calculation CDQ0000002014000024, "Seismic Dam Failure Simulations Calculation."
- 2. The 25-year and 500-year flood inflow calculations (as referenced in LAR Enclosure 4, Section 2.4.4.1) are contained in calculations, CDQ0000002014000029, "Inflow Volume Analysis for Seismic Events Calculation," and CDQ0000002014000030, "Inflow Hydrograph Development for Seismic Events."
CNL-20-082 E1-4 of 4
SECURITY RELATED INFORMATION AND PROPRIETARY INFORMATION-WITHHOl:-D UNDER 10 CFR 2.390 Enclosure 2 DVD Containing the Information Requested In Enclosu*re 1 (Security Related Information)
Barge Design Solutions (Barge) Software Dedication Report (SOR), PMP Evaluation Tool Package, SOR 16-01, Revision 2 (For RAI 2.4-2.2*.c) .
- (Proprietary Information) .
. CNL-20-082 SECURITY RELATED JNFORMATION AND PROPRIETARY *INFORMATION ....
WITflHOLD.UNDER 10 CFR 2.390 -
Enclosure 3 Flowchart of Calculations CNL-20-082
HEC-HMS/HEC-RAS 2012 LAR Ca lculations 2014 LAR Calculations 2015 FHRR Calculations WBU tocal lrtense PredpitationAnatysis EXCE L HEC-RAS CIXl.2013-163 n
Main Stem lnitQI Main Stem Unsteady Dam Rath-g ClJr.e Flow RUe Calwlatioo None Cak:Uation cocuon-01*
r-+ CDQ20U-05 ° I Flood Operational
~ '---.----'J-EXCEL Guide s Calwlation Initial Dam Rating CDQ2008-50
, -~
Cl.lVt! Ctlrulations
~
HEC-RAS HEC-RAS HEC-RAS HEC-RAS crxuooe-01 tlYu n EXCEL HEC-RAS HEC-RASPMF Uncertaintv Seisnic Dam Failure Sunny Day Dam
~
Trib utary lnit~I Dam SinUations SinUatiora smtJattons Failure Simulations
-- I -
Rating Curve Tributary Unsteady Flow RUe Calrulation Cak:uiation - Cak:Uation CabJation - Cak:ulations ~
Cak:Uation I---+ CDQ2014- t9*
HEC-RAS CDQ2014-23 CDQ2014-32 CDQ2014-24 CDQ2014-25 & 28
~
C00,2014-16*
~ ~ HEC-RAS f.ltodel Setup Calw lat ion I-+ C00.20 14-21'"
ArcGIS/EXCH ArcGIS/EXCH HEC-RAS HEC-RASTribJtary Exa,I Exa,I Ard:31S/Excel Reservoir Ster age HEC-RASTributary Exa.l Ca~bration Tab~s Calculation Geometry Calculation I---+ Cak:Uation Unit H'l(lrccraph Inflow 1-tfdrograph
-*,:::,-.--;r-COQ.2003-51 C0Q2014-17 \Vind Wave l CDQ2014-18 Adjustment lnfk>ws Calct.fation Deve6opment for calculation
~
~
Seismic Events
~ calculation CDQ2014-15 CDQ.2014-33 CDQ2014-12 r+ calc.Uation
~
CDQ2014-30
~
Ar<GIS/EXCEL SOCHGeanetry SOCH/H EC-RAS
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Verification SOCH calibration ArcGIS/EXCEL HEC~RA.S calculations calculations
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HEC-RA.SMainStem CDQ2008-24 ttru 26 CDQ.2008-36 tt-r-u 42 HEC-RAS Main Stem CDQ2008-29 ttru 30 L+ Geomet ry Calculat ion Calibration Arc.GIS/Excel Exa. l I---+ Cak:ulation
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CDQ.2012--04
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CDQ.2012-06 CU"ve t,i.imber
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EXCEL Precipitat ion HEC-HMS/FLOHD'tRO UnitH',dr~raphs ~
Determination calculation CDCl.2014-14 - ~
Basefk>w r.a lcUation CDQ.20 14-13 f---
Exa. l cak:ulations COQ2008-S6 ttru 73, lnfk>wVolume CDQ.2008-49 & 55 91 Anatvsls For Seismic Events calculation
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CDQ.2014-29
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EXCEL FlDHYDRO/EXCEL PMFlnflow API f.alcUation Determinat ion CDQ2008-S2 . calculation CDQ2008-S3
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- calculation re'w'ised to inck.lde adcftional info rmation for FHRR
{no LAR irTl)act) 2020 LAR Calculations CNL-20-082 E3-1of3
2012 LAR Calculations 2014 LAR Calculations 2015 FHRR Calculations HEC-HMS/FlDHOVRO HEC-RAS Unit H',drcaraphs COQ20Q3-56 th'u 73, HEC-RAS Model trtlows Cak:Uation 91 Set~ Calrulation CDQ2014- 15 COQ.2014-21*
2020 LAR Calcu lations U HT~~~~~~n for 1------....L--~~ ChictamaLga Drain BFNWa m ingTlme CDQ.2016-47 Down CCXl.2017-72 CDQ.2017-81 Basin PMP and UP CDQ201&-41
\VON 9:l.N Warning Time CIXl.2017-76 PCAT "'1ode1Set-op CDQ.2017-80 ProjectPMF Calc:Uations PMF Slrnma ry Desie n Storm Coo.2017-SS-62, 64, Cak:ulation Tel1l)oral Rarlfall 64, 67-69, 71, 73-75, CDQ2017-70 DlstriblA:ion n .78 CDQ2015-34 API Dell!rmination WndWavesfor Combined Effect CDQ20 1&-4S Fbods CDQ2014-33 Week~ Baseflow Dete rm ination CDQ201&-42 CN L-20-082 E3-2 of3
Topical Report Calrulation Gridded PMP Development Controlling PMF Calculation CDQ2017-59 CDQ2016-41 Calculation Item IR 2.4-2 (la)
COQ2016-44 ltem lR 2.4-2 (3b)
SPAS Data User Input (D...-ation) ltemlR 2.4-4 (1)
ControNing PMFTabular Sub-Basin PMP Rainfall PMP Basin Depths for COQ2017-80 Controling PMF COQ2016-41 Telll)oral Output :
Calculation:
Appendix F & H Dist ribution COQ.2017-59 COQ2017-S9 Tool ls located in cak:Uation Appendix B-A Appendix 8 COQ2017-80
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Append~ B Table6.2.l
~I ~ ~
Item IR 2.4-2 (le) ltem lR 2.4-2 (la) User Input (Sasins)
Item IR 2.4-4 (S)
User Input (sta,m twes) ltemlR 2.4-4 (3)
NatiDnat lnwntoryof Dam s Dat;,i Application CCXl.2016-44 Exczss Precipitation calwlatlons CCXU016-41 SectiCll 3.3 Appendix A-A Output:
Ou11>ut,
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calcUation Tool is located ii COQ2017-59
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cak:ulation Tool is k>cated in COQ.2017.SO CIXl.2017-59 Appendix 8 -A ....... COQ2017-80 Appendix 8-A 06_NID
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Appendix( 01 API cak.llation
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ltemlR2.4-2 (1d)
User Input (Fu l Basin)
CCXl.201644 ltem lR2.4-4 (2)
AppendixA-8 Unit H','d rOHraph (.alcul atlons ltemlR 2.4-4 (S)
Inflow t-tvdrograph Di stribution
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COQ2017-59 Output:
Appendix 8 ...
Calculation Tool is klcated ii CDQ.2017*59 ltemlR 2.4-2 (2a) 02_HEC-HMS_unit_h-,drographs COQ2017-80 Appendix B*A Sub-basin Text FIie ~ Appe nd~ I PMFSummary CDQ.20 16-44 1 ~
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Calculation (00,2017 *70
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Item IR 2.4-4 (S) ltemlR 2.4-4 (SJ Con troling PMF Ral'l-on--Rese rvoir Calwlations Stream Cot.l'se Model ltemlR 2.4* 2 (l b)
Output :
PMP Scenario Autanatim CDQ.2017-S9 Calculation Tool is loalled r1 COQ20l7-S9 Base Python Saipt Appendix B-A COQ20 17-80 Appendix 8-A OB_HEC-RAS 03_ROR_calculation
-r CIXl,2016-44 Appendi,c E
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AppendiJCA-F Topical Report PMP Tool ltemlR 2.4-2 {2c)
Modfied PMP Tool
~ Item IR 2.4-2 (2b) Item IR 2.4-4 (S) ltemlR2.4-4(S)
CootroNing PMF PMP Scenario Autanatim Surface R~df and Baseflow Calctiaticm Resu lts Data COQ2016-41 PMPTool SOR Event Specific: Pythoo Script AppendiJCO Attachment 9 CDQ.2017-S9 COQ20 16--44 COQ2017-59 calciJation Tool is located i Appendi,c 8-A Appendi,c 8-A
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COQ2017*80 04_Surfa01!_n,ioff_scalirg_
09_0utputGra~ics AppendiJC F and baseflow
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ltemtR 2.4-2 (3a)
Saipt for generatSlg TI N and calculatirw primary basin rainfan 1temlR 2.4-4 (S)
Tributary Inflow Routing COQ2016-44
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Output :
Calculation Tool is located i"I COQ2017-59 COQ.2017-80 Appendi,c 8-A ,___
AppendbtG OS_Routing ltem lR 2.4-2 (2d) l R2.4-3 Item IR 2.4-2 (2d)
'--- ____,,,,---.. ~
UP Rainfall UP Model File s lte m 2.4-S{2) Item 2.4-5{2) ltem2 .4-S(l)
Rainfall Q lru latioo Resul ts Seismic lnftows Seisrnk ln ftows Seisrric HEC-RAS Files COQ2016-41 CDQ2013-S7 lrtlow l+{drograph Section S.4.4 lnfklwVoh..me Seisrric Dam Failure Appendix F CDQ.2016-44 Development for Table 14 Ana¥sis For Seismic
- Si-nulat ions
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Seismic Events Events Calculation CalciJation
~ ~ COQ2014-29 CalciJation CDQ20 14-30 (00,20 14-24 E3 -3 of3 ~ ~ ~
CNL-20-082
Enclosure 4 Barge Design Solutions Affidavit CNL-20-082
.AFFIDAVIT STATE OF TENNESSEE)
)ss.
COUNTY OF DAVIDSON)
- 1. My nam.e is Carrie Stokes. I am Senior Vice President, for Barge Design Solutions, rnc. and as such I am authorized to execute this Affidavit.
- 2. I am familiar with the criteria applied by Barge Design Solutions, Inc. to determine
- whether certain Barge Design Solutions, lnc. information is a trade secret, proprietary, and commercially sensitive. I am familiar with the policies established by Barge Design SoJutions, Inc.
to ensure the proper application of these criteria.*
- 3. I am familiar with the Barge Design Solutions, Inc. information contained !n the report:
"Software Dedication Report, PMP Evaluation Tool Package, SOR 16-01" dated September 2020 and referred to herein as "Dedication Report." lnformatio_n regarding the dedication methodology and test problem suite has b~en *classified by Ba_rge Design Solution.s, Inc.
as proprietary and a trade secret in accordance with. the policies established by Barge Design Solutions, Inc. for the .control and protection of proprietary information in furtherance of the busin~ss of Barge Design Solutions, Inc ..
- 4. This Dedication Report contains trade secrets and information of a proprietary nature of the type cu.stomarily held In c:onfidence by Barge Desigr:i Solutions, Inc. and not made availal?le tc;, the public. f3a'sep on my experience! I am aware that other companies regard information of the kind contained in this Dedication Report as oommerdally sensitive, trade secrets, proprietary, and confidential.
- 5. This Dedication Report has been made available to the U.S: Nuclear Regulatory Commission .in confidence with the request th~t the information contained lri this Document be withheld ~rom public disclosure. The request for withholding of prqprifltary Information is made
in accordance with 10 CFR 2.390. The Information for which withholding from disclosure is requested qualifies under 10 CFR 2.390(a)(4). "Trade secrets and commercial or financial information."
- 6. The following criteric! are customarily c.)pplied by Barge Design Solutlo~s! Inc. to determine whether information should be classified as proprietary:
(a) The lnformatio_n reveals *details of Barge Design Sol.utions, lnc.'s research and development processes or their results.
(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
(c) The infqrmation ,nclu.des test data or analytical techniques concerning a process, meth9dology,.or component.
- (d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides *a competitive advantage for B-arge Design Solutions, inc. in product optimization or marketability:
(e) The information is vital to a competitive advantage held by.Barge Design Solutions, Inc., would be helpful to competitors; and would likely cause substantial harm to the competitive position of Barge Design Solutions, Inc.
The information in the Dedication Report is considered proprietary for the re~s9ns set forth In paragraphs G(a) - G(e) above.
- 7. In accordance with Barge c;>esign Solutions, lnc.'s policies governing the protection:
and control of Information, trade secrets and confidential or proprietary information contained in this Dedication Report have been *made* available, on a limited basis, to others outside Barge
- Design Solutions, Inc. only as requirE:;d and under suitable agreement providing for nondisclosure and limited use of the information.
- 8. Barge Desig,:i Solutions, Inc. policy requires t_hat proprietary Information be kept in a secu'red file or ar~a and distributed on a n~ed-to-know basis.
- 9. The foregoing statements are true and correct to the b.est of my knowledge, information, and belief.
FURTHER AFFIANT SAYETH NOT;
- 6. 1/4 SUBSCRIB~D before me this---'-"""-_ _ _ day of *
("\,.,-\ -
~Der * . .c90~0 '
My Commission Expires: